US4405558A - Nuclear reactor shutdown system - Google Patents

Nuclear reactor shutdown system Download PDF

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Publication number
US4405558A
US4405558A US06/197,380 US19738080A US4405558A US 4405558 A US4405558 A US 4405558A US 19738080 A US19738080 A US 19738080A US 4405558 A US4405558 A US 4405558A
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US
United States
Prior art keywords
reactor
temperature
coil
temperature sensitive
reactor coolant
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Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
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US06/197,380
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English (en)
Inventor
James D. Mangus
Martin H. Cooper
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CBS Corp
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Westinghouse Electric Corp
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Publication date
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Priority to US06/197,380 priority Critical patent/US4405558A/en
Assigned to WESTINGHOUSE ELECTRIC CORPORATION reassignment WESTINGHOUSE ELECTRIC CORPORATION ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: COOPER MARTIN H., MANGUS JAMES D.
Priority to GB8127230A priority patent/GB2085642B/en
Priority to DE19813140272 priority patent/DE3140272A1/de
Priority to JP56162887A priority patent/JPS5796290A/ja
Priority to FR8119362A priority patent/FR2492150B1/fr
Application granted granted Critical
Publication of US4405558A publication Critical patent/US4405558A/en
Anticipated expiration legal-status Critical
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to automatic control systems for nuclear reactors and more particularly to inherent shutdown systems for nuclear reactor control rods.
  • All nuclear reactors incorporate an emergency shutdown system which comprises a device for reducing the reactivity of the nuclear reactor core.
  • the reduction in reactivity of the nuclear reactor core is generally accomplished by way of introducing a form of neutron absorbing material into the nuclear reactor core.
  • the systems are intended to be simple and reliable systems for quickly introducing neutron absorbing material into the core of the nuclear reactor for effecting a shutdown of the reactor.
  • the basic method known in the prior art for controlling a nuclear reactor is the system comprising control rods. In this system, the control rods are raised and lowered by mechanical mechanisms into and out of the nuclear reactor core for controlling the amount of reactivity in the core.
  • the apparatus comprises a restraint mechanism for releasably restraining a multitude of discrete bodies of materials which are magnetic and possess neutron absorbing properties.
  • the restraint means comprises at least one pair of magnetic pole pieces of opposite polarity, the apparatus being operated to release the discrete bodies by demagnetization of the pole pieces whereby the bodies are moved under the influence of gravity into the core of the reactor.
  • the neutron absorbing balls are dropped into the reactor core thereby reducing the reactivity of the nuclear reactor core.
  • Still another alternate method of reactor control comprises the use of a Curie point material which when heated to the Curie point loses substantially all of its magnetic susceptibility thereby causing an activation of the control system.
  • the neutron absorber material is restrained and supported by a magnet whose lines of force are linked by a yoke.
  • the yoke is of a ferromagnetic material having a Curie point at the critical level and in contact with the reactor coolant. When the reactor coolant temperatures reaches the critical level, the yoke will be at its Curie point and thereby will lose its magnetic susceptibility releasing the neutron absorbing material into the core of the nuclear reactor.
  • the yoke When cooled, the yoke regains its magnetic susceptibility thereby allowing the magnetic latch to be reused.
  • One difficulty with the Curie point type systems is that the Curie material requires a relatively long time to heat to the Curie point due to the mass of the components. The slowness of response time of the Curie material may result in the inability of the reactor shutdown system to respond quickly.
  • the nuclear reactor shutdown system comprises a temperature sensitive device connected to a magnetic latch of a neutron absorbing mechanism.
  • the temperature sensitive device is disposed in the neutron absorbing mechanism in such a manner that it is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause the magnetic latch to open and allow neutron absorbing material to enter the reactor core.
  • the temperature sensitive device comprises temperature sensitive material which may be a temperature sensitive resistor sometimes referred to as a thermistor.
  • the thermistor is a device wherein its resistivity significantly increases with increase in its temperature such that when its temperature has significantly increased, the current passing through this system substantially decreases.
  • the resistivity in the temperature sensitive material significantly increases to the point where little electricity flows through the circuit thereby causing the magnetic field in the magnetic latch to fall to a level at which the magnetic latch opens thereby inserting neutron absorbing material in the reactor core.
  • FIG. 1 is a cross-sectional view in elevation of a nuclear reactor
  • FIG. 2 is a cross-sectional view in elevation of a magnetic latch of a control rod drive mechanism in the latched position
  • FIG. 3 is a cross-sectional view in elevation of the magnetic latch of a control rod drive mechanism in the open position
  • FIG. 4 is a detailed view of the thermistor arrangement.
  • the nuclear reactor is referred to generally as 10 and comprises a reactor vessel 12 having an inlet 14 and an outlet 16 disposed thereon.
  • a core 18 is disposed within reactor vessel 12 and is surrounded by reactor coolant 20 which may be a liquid metal such as liquid sodium. Core 18 has a central region 22 wherein the greatest reactivity of the core occurs.
  • the reactor core 18 comprises a plurality of fuel assemblies 24 which may be chosen from those well known in the art. Fuel assemblies 24 are supported by lower core support 26 which may be attached to the bottom of reactor vessel 12 by means of supports 28. Lower core support 26 defines an inlet plenum 30 therewithin.
  • a flow directing means such as conduit 32 may be attached to inlet 14 and to lower core support 26 for conducting the reactor coolant through inlet 14 and into inlet plenum 30.
  • Fuel assemblies 24 have first openings 34 disposed in the lower section thereof and in fluid communication with inlet plenum 30 such that the flow of reactor coolant 20 through inlet plenum 30 may enter fuel assemblies 24. Once the reactor coolant has entered fuel assemblies 24, the coolant flows upwardly through fuel assemblies 24 and out through the top thereof. In this manner, heat is transferred from fuel assemblies 24 to reactor coolant 20 in a manner well understood in the art.
  • control assemblies 36 are also disposed within reactor vessel 12 and within core 18.
  • Control assemblies 36 are basically arranged similar to fuel assemblies 24 except they are also arranged to accommodate the insertion of control rods (not shown).
  • control rod drive mechanism 38 is referred to generally as 38 and comprises an outer housing 40 through which is disposed a drive member 42.
  • Drive member 42 may be a cylindrical metal member which is attached at its lower end to latching mechanism 44 and at its upper end to a drive means (not shown).
  • Latch mechanism 44 comprises a ferromagnetic upper member 46 having a bore 48 therethrough. Bore 48 is provided to allow reactor coolant 20 to flow upwardly through control rod drive mechanism 38.
  • a coil 50 is disposed in upper member 46 such that it is disposed around bore 48. Coil 50 is connected to electrical instrumentation and power sources located externally of reactor vessel 12 by means of hermetically sealed electrical line 52.
  • Upper member 46 also has a first contact member 54 attached thereto which may be a conical type member disposed around a portion of upper member 46 such that it is aligned concentrically with bore 48.
  • a ferromagnetic lower member 56 which may be a cylindrical member is slidably disposed around upper member 46 such that it may slide vertically relative to upper member 46.
  • Lower member 56 has a second contact member 58 attached thereto in a manner so as to be able to contact first contact member 54 when brought into contact therewith.
  • coil 50 When coil 50 is energized and first contact member 54 is in contact with second contact member 58, an electromagnetic attraction is developed therebetween which causes upper member 46 to be magnetically latched to lower member 56.
  • a plurality of control rods 60 which are comprised of neutron absorbing material are attached to the lower end of lower member 56 and are arranged so as to be able to be inserted into control assembly 36 when lower member 56 is lowered relative to upper member 46.
  • a cylindrical guide tube 62 is attached to the bottom of lower member 56 and disposed around control rods 60 so as to guide lower member 56 when it is lowered.
  • a first sleeve 64 is also disposed within housing 40 and around guide tube 62 for increasing the guidance of guide tube 62 when it is lowered or raised.
  • a tubular member 66 is disposed within drive member 42.
  • Tubular member 66 is also arranged so that line 52 may be disposed therein.
  • a plurality of conduits 68 are attached to drive member 42 and tubular member 66 so as to provide channels through which reactor coolant 20 may flow into and out of tubular member 66.
  • a temperature sensitive device 70 is disposed in line 52 and arranged in tubular member 66 so as to be near the junction of conduits 68. This arrangement allows the flow of reactor coolant 20 to contact temperature sensitive device 70 so that temperature sensitive device 70 may have the same temperature as reactor coolant 20.
  • temperature sensitive device 70 comprises a temperature responsive resistor 72 which is connected electrically by means of electric lines 74 to coil 50 and to electrical instrumentation located outside of reactor vessel 12.
  • Temperature responsive resistor 72 is sometimes referred to as a thermistor and has the characteristic that when its temperature increases, its resistivity also increases.
  • Temperature responsive resistor 72 may be chosen from those well known in the art such as one from Fenwal Electronics. Temperature responsive resistor 72 has the advantage of responding to the reactor coolant temperature in a much quicker manner than a Curie point material.
  • the resistivity of the temperature responsive resistor 72 will increase to the point where the electrical current carried by lines 74 to coil 50 will be reduced to a level whereby magnetic latch 44 will be opened. The opening of magnetic latch 44 will cause lower member 56 to drop into the reactor core under the influence of gravity thereby shutting down the nuclear reactor.
  • the resistivity of the temperature responsive resistor 72 will also be lowered to the point where the electricity in the lines 74 will be returned to its normal level.
  • drive member 42 may be lowered such that first contact member 54 contacts second contact member 58.
  • control rod drive mechanism 38 is arranged as shown in FIG. 2 such that upper member 46 is connected to lower member 56 by means of an electromagnetic attachment. Since reactor coolant 20 is continuously flowing through reactor vessel 12 and through control rod drive mechanisms 38, reactor coolant 20 flows upwardly through housing 40 and through bore 48. In addition, reactor coolant 20 flows through conduit 68 and into contact with temperature sensitive device 70. The flow of reactor coolant 20 around temperature sensitive device 70 causes the temperature of temperature sensitive device 70 to become that of the reactor coolant 20. In turn, temperature responsive resistor 72 also attains the temperature of temperature sensitive device 70 and of reactor coolant 20. Under normal operating conditions, the temperature of reactor coolant 20 and temperature responsive resistor 72 is such that the resistivity of temperature responsive resistor 72 is low.
  • drive line 42 may be lowered such that first contact member 54 comes into contact with second contact member 58.
  • the magnetic flux of coil 50 is reestablished through upper member 46 and lower member 56 such that first contact 54 and second contact 58 are joined magnetically.
  • drive line 42 may be raised which causes upper member 46 and lower member 56 to be raised to a position as shown in FIG. 2.
  • the control rod drive mechanism 38 is in its original position.
  • the nuclear reactor shutdown system provides a mechanism for automatically, safely, and quickly shutting down a nuclear reactor in response to an overtemperature condition of the nuclear reactor coolant.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US06/197,380 1980-10-15 1980-10-15 Nuclear reactor shutdown system Expired - Lifetime US4405558A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
US06/197,380 US4405558A (en) 1980-10-15 1980-10-15 Nuclear reactor shutdown system
GB8127230A GB2085642B (en) 1980-10-15 1981-09-09 Nuclear reactor shutdown system
DE19813140272 DE3140272A1 (de) 1980-10-15 1981-10-10 "abschaltsystem fuer kernreaktoren"
JP56162887A JPS5796290A (en) 1980-10-15 1981-10-14 Nuclear reactor shutdown device
FR8119362A FR2492150B1 (fr) 1980-10-15 1981-10-14 Systeme pour arreter le fonctionnement d'un reacteur nucleaire

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/197,380 US4405558A (en) 1980-10-15 1980-10-15 Nuclear reactor shutdown system

Publications (1)

Publication Number Publication Date
US4405558A true US4405558A (en) 1983-09-20

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Family Applications (1)

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US06/197,380 Expired - Lifetime US4405558A (en) 1980-10-15 1980-10-15 Nuclear reactor shutdown system

Country Status (5)

Country Link
US (1) US4405558A (ja)
JP (1) JPS5796290A (ja)
DE (1) DE3140272A1 (ja)
FR (1) FR2492150B1 (ja)
GB (1) GB2085642B (ja)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4576781A (en) * 1981-07-28 1986-03-18 United Kingdom Atomic Energy Authority Temperature threshold detectors
US4654192A (en) * 1984-03-13 1987-03-31 The United States Of America As Represented By The United States Department Of Energy Temperature actuated automatic safety rod release
US4734252A (en) * 1986-08-07 1988-03-29 The United States Of America As Represented By The United States Department Of Energy Nuclear reactor shutdown control rod assembly
US5114663A (en) * 1990-08-16 1992-05-19 Doryokuro Kakunenryo Kaihatsu Jigyodan Electromagnet for nuclear reactor shutdown system
WO2003088264A2 (en) * 2002-04-12 2003-10-23 Bechtel Bwxt Idaho, Llc Automatically scramming nuclear reactor system and method
US9280516B2 (en) 2011-04-07 2016-03-08 The University Of Western Ontario Method and system to validate wired sensors

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3341540A1 (de) * 1983-11-17 1985-05-30 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Inhaerent sicheres abschaltsystem fuer kernreaktoren
GB9017682D0 (en) * 1990-08-13 1990-09-26 Nnc Ltd Nuclear reactors
DE4441751C1 (de) * 1994-11-23 1996-04-25 Siemens Ag Schnellabschaltsystem und Verfahren zur Schnellabschaltung eines Kernreaktors

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US2931763A (en) * 1956-08-03 1960-04-05 Honeywell Regulator Co Control apparatus
US3115453A (en) * 1961-08-02 1963-12-24 Paget John Arthur Emergency shutdown for nuclear reactors
US3147188A (en) * 1959-07-20 1964-09-01 Atomic Energy Authority Uk Reactor shut-down apparatus using neutron absorbing balls
US3170842A (en) * 1961-11-06 1965-02-23 Phillips Petroleum Co Subcritical borehole nuclear reactor and process
US3194740A (en) * 1956-09-19 1965-07-13 Westinghouse Electric Corp Nuclear reactor
DE1210500B (de) * 1960-10-06 1966-02-10 Kernforschung Gmbh Ges Fuer Stossimpulsgeber fuer Abschaltvorrichtungen von Kernreaktoren
US3784788A (en) * 1971-05-04 1974-01-08 Belling & Co Ltd Electric liquid boiling apparatus having an electronic temperature sensor control
US3940309A (en) * 1972-04-14 1976-02-24 Comitato Nazionale Per L'energia Nucleare Electromagnetic safety device for the suspension of the rods in a nuclear reactor
US3976540A (en) * 1975-04-03 1976-08-24 The United States Of America As Represented By The United States Energy Research And Development Administration Magnetic latch trigger for inherent shutdown assembly
US4073681A (en) * 1975-03-05 1978-02-14 General Atomic Company Nuclear reactor shutdown system
US4104507A (en) * 1977-01-14 1978-08-01 Design & Manufacturing Corporation PTC heater for enhancing thermal actuator response
US4139414A (en) * 1977-06-10 1979-02-13 Combustion Engineering, Inc. Scram device having a multiplicity of neutron absorbing masses
US4304632A (en) * 1979-08-20 1981-12-08 Westinghouse Electric Corp. Nuclear reactor shutdown system

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2230984B1 (ja) * 1973-05-22 1976-04-23 Electricite De France
FR2283570A1 (fr) * 1974-09-02 1976-03-26 Unelec Dispositif de protection thermique
US4204909A (en) * 1977-06-10 1980-05-27 Combustion Engineering, Inc. Temperature sensitive self-actuated scram mechanism

Patent Citations (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2931763A (en) * 1956-08-03 1960-04-05 Honeywell Regulator Co Control apparatus
US3194740A (en) * 1956-09-19 1965-07-13 Westinghouse Electric Corp Nuclear reactor
US3147188A (en) * 1959-07-20 1964-09-01 Atomic Energy Authority Uk Reactor shut-down apparatus using neutron absorbing balls
US3483082A (en) * 1960-10-06 1969-12-09 Kernforschung Gmbh Ges Fuer Nuclear reactors shutdown
DE1210500B (de) * 1960-10-06 1966-02-10 Kernforschung Gmbh Ges Fuer Stossimpulsgeber fuer Abschaltvorrichtungen von Kernreaktoren
US3115453A (en) * 1961-08-02 1963-12-24 Paget John Arthur Emergency shutdown for nuclear reactors
US3170842A (en) * 1961-11-06 1965-02-23 Phillips Petroleum Co Subcritical borehole nuclear reactor and process
US3784788A (en) * 1971-05-04 1974-01-08 Belling & Co Ltd Electric liquid boiling apparatus having an electronic temperature sensor control
US3940309A (en) * 1972-04-14 1976-02-24 Comitato Nazionale Per L'energia Nucleare Electromagnetic safety device for the suspension of the rods in a nuclear reactor
US4073681A (en) * 1975-03-05 1978-02-14 General Atomic Company Nuclear reactor shutdown system
US3976540A (en) * 1975-04-03 1976-08-24 The United States Of America As Represented By The United States Energy Research And Development Administration Magnetic latch trigger for inherent shutdown assembly
US4104507A (en) * 1977-01-14 1978-08-01 Design & Manufacturing Corporation PTC heater for enhancing thermal actuator response
US4139414A (en) * 1977-06-10 1979-02-13 Combustion Engineering, Inc. Scram device having a multiplicity of neutron absorbing masses
US4304632A (en) * 1979-08-20 1981-12-08 Westinghouse Electric Corp. Nuclear reactor shutdown system

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Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4576781A (en) * 1981-07-28 1986-03-18 United Kingdom Atomic Energy Authority Temperature threshold detectors
US4654192A (en) * 1984-03-13 1987-03-31 The United States Of America As Represented By The United States Department Of Energy Temperature actuated automatic safety rod release
US4734252A (en) * 1986-08-07 1988-03-29 The United States Of America As Represented By The United States Department Of Energy Nuclear reactor shutdown control rod assembly
US5114663A (en) * 1990-08-16 1992-05-19 Doryokuro Kakunenryo Kaihatsu Jigyodan Electromagnet for nuclear reactor shutdown system
WO2003088264A2 (en) * 2002-04-12 2003-10-23 Bechtel Bwxt Idaho, Llc Automatically scramming nuclear reactor system and method
WO2003088264A3 (en) * 2002-04-12 2004-09-23 Bechtel Bwxt Idaho Llc Automatically scramming nuclear reactor system and method
US9280516B2 (en) 2011-04-07 2016-03-08 The University Of Western Ontario Method and system to validate wired sensors

Also Published As

Publication number Publication date
JPS5796290A (en) 1982-06-15
GB2085642B (en) 1983-11-09
GB2085642A (en) 1982-04-28
DE3140272A1 (de) 1982-07-22
JPS6412352B2 (ja) 1989-02-28
FR2492150A1 (fr) 1982-04-16
FR2492150B1 (fr) 1988-04-01

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